Nenhuma / A implantação de um repositório para rejeitos radioativos é um projeto multidisciplinar que demanda além de especialistas de diferentes áreas do conhecimento, a interação com instituições públicas e privadas, dados e informações relacionadas com rejeitos radioativos, geologia, tecnologia etc. Todas as atividades devem estar em conformidade com as normas, requisitos e procedimentos, incluindo a legislação nacional e internacional. A manutenção dos registros de inventário dos rejeitos é um requisito importante regulamentar e deverá estar disponível até mesmo após o encerramento do repositório. O Centro de Desenvolvimento da Tecnologia Nuclear CDTN está coordenando o projeto para a construção do repositório nacional para o armazenamento dos rejeitos de baixo e médio nível de radiação. A fim de consolidar todas as informações que serão provenientes deste projeto, está sendo desenvolvido e implantado no CDTN um sistema Gerenciador de banco de dados, chamado de Sistema de Gestão Integrada de dados para Repositórios de Rejeitos Radioativos (SGI3R), que também vai gerenciar todos os dados de trabalhos anteriores realizados no Brasil e em todo o mundo sobre este assunto. A proposta é criar uma estrutura de módulos, tendo como base oito módulos: inventário, seleção de sites, tipos de repositório, tecnologia, parceiros, legislação, comunicação e documentos. O SGI3R compreende a integração (inclusão, atualização e exclusão), processamento de dados, padronização e consistência entre os processos. O SGI3R dará apoio às etapas deste projeto, que permitirá a preservação de todas as informações disponíveis, evitando a duplicação de esforços e custos adicionais, melhorando, deste modo, o projeto de planejamento e execução. Adicionalmente o SGI3R permitirá o acesso às informações para todas as partes interessadas. / The implantation of a repository for radioactive wastes is a multidisciplinary project that demands in addition to specialists of different areas of knowledge, interaction with public and private institutions, data and information related to radioactive wastes, geology, technology etc. All the activities must be in accordance with norms, requirements and procedures, including national and international legislation. The maintenance of the waste inventory records is an important regulatory requirement and must be available even after the closure of the repository. The Center of Nuclear Technology Development CDTN is coordinating the Project for the construction of the national repository to store the low and intermediatelevel wastes. In order to consolidate all information that will come from this Project, it is being developed and implanted in CDTN a manager system of database, called Integrated Management System of data for Radioactive Waste Repositories (SGI3R), which will also manage all data from previous works carried out in Brazil and around the world about this subject. The proposal is to build a structure of eight modules: Inventory, Site Selection, Types of Repository, Documents, Technology, Partners, Legislation, and Communication, having initially as base the first four ones. The SGI3R comprises the data processing (inclusion, update and exclusion), integration, standardization, and consistency among the processes. The SGI3R will give support to the stages of this Project, which will allow the preservation of all the available information, preventing duplication of efforts and additional costs, improving, in this way, the Project planning and execution. Additionally the SGI3R will make possible the information access to all stakeholders.

Neste trabalho foi avaliada a dose efetiva recebida pelos trabalhadores da Gerência de Rejeitos Radioativos do IPEN devido à inalação de 222Rn nos galpões de armazenamento de rejeitos radioativos tratados e não tratados. As concentrações de 222Rn no interior dos galpões foram determinadas por meio da técnica de detecção passiva com detectores de traços nucleares do estado sólido (SSNTD). O detector utilizado foi o CR-39 inserido em uma câmara de difusão do tipo NRPB. Foram monitorados um total de 12 pontos internos e 1 ponto externo no galpão de rejeitos radioativos tratados G4 e 13 pontos no galpão de rejeitos radioativos não tratados G3, durante um período de 11 meses, entre junho de 2012 e maio de 2013. As concentrações variaram de 0,73 ± 0,08 e 4,55 ± 0,16 kBqm-3 entre os períodos de monitoramento no galpão G4 e entre 0,61 ± 0,07 e 2,94 ± 0,12 kBqm-3 no galpão G3. A dose efetiva devido à inalação de 222Rn no interior dos galpões de rejeitos radioativos foi calculada de acordo com os procedimentos da Comissão Internacional de Proteção Radiológica (ICRP) a partir de um fator de conversão de dose, da concentração média do 222Rn no ar e do tempo de exposição dos indivíduos. Os valores de doses apresentados são uma média das concentrações entre os períodos de monitoramento que variam 15,70 mSva-1 no G4 e de 9,27 mSva-1 no G3, sendo que em um dos períodos obteve-se valores superiores ao estabelecidos pelo órgão regulador (CNEN) e recomendados pela Comissão Internacional de Proteção Radiológica (ICRP) de 20 mSva-1 para indivíduos ocupacionalmente expostos, indicando a necessidade de medidas mitigadoras. Cabe, contudo, informar que foi considerada uma hipótese bastante conservativa de 2000 horas de trabalho no local. / Some radionuclides that make up the radioactive series are noted for their contribution to the total exposure to which individuals are subjected, an important example is known as radon 222Rn and their descendants, responsible for more than half of the radiation dose received by the population due to natural sources. In this work the effective dose received by the workers of the Management of Radioactive Waste in IPEN due to inhalation of 222Rn in storage sheds from treated and untreated radioactive waste was evaluated. Concentrations of 222Rn inside the sheds of treated and untreated radioactive waste G3 and G4 were determined by the technique of passive detection with solid state nuclear track (SSNTD) detectors. The detector used was CR-39 inserted in a diffusion chamber type NRPB. A total of 12 internal points and 1 external point were monitored in the shed radioactive waste treated G4 and 13 points in the shed radioactive waste untreated G3, for a period of 11 months between June 2012 and May 2013. Concentrations ranged 0.73 ± 0.08 to 4.55 ± 0.16 kBqm-3 among the monitoring periods in the shed G4 and between 0.61 ± 0.07 and 2.94 ± 0.12 kBqm-3 in the shed G3. The effective dose due to inhalation of 222Rn inside the sheds radioactive waste was calculated according to the procedures of the International Commission on Radiological Protection (ICRP) from a conversion factor of dose, the mean concentration of 222Rn in the air and time of exposure of individuals. The dose values for G4 and G3 are 15.70 and 9.27 mSva-1 respectively, this being greater than the value established by the National Nuclear Energy Commission (CNEN) and recommended by the International Commission on Radiological Protection (ICRP) 20 mSv / a for occupationally exposed individuals, thus indicating the need for mitigation measures. It should, however, report that was considered a very conservative assumption of 2,000 hours of work on site.

A deposição de rejeitos radioativos em repositórios geológicos profundos vem sendo estudada nos últimos anos em diversos países. Materiais à base de cimento são utilizados nesses repositórios como material estrutural, matriz de imobilização de rejeitos ou material de preenchimento. Compreender o desempenho desse material é essencial para garantir a segurança da instalação durante o seu tempo de vida útil (de milhares a centenas de milhares de anos, dependendo do tipo de rejeito). Este trabalho objetiva modelar o comportamento em longo prazo do cimento Portland e estudar a influência de diversos fatores na hidratação e na evolução desse material. A modelagem descritiva abordou a hidratação do cimento nas condições ambientais esperadas no repositório e os efeitos desses fatores em propriedades mecânicas, mineralógicas e morfológicas do cimento. Os fatores ambientais considerados relevantes neste trabalho foram: alta temperatura e pressão, penetração de água subterrânea contendo íons quimicamente agressivos ao cimento e a presença do campo de radiação proveniente dos rejeitos. Ensaios acelerados de degradação também foram realizados para corroborar com o modelo descrito. Observou-se uma sinergia entre diversos fatores na degradação do cimento, como a influência da temperatura e da radiação em reações deletérias ao material. O resultado da modelagem apontou três principais possíveis causas de falha nas barreiras artificiais: a) a formação de um caminho preferencial; b) a perda de resistência e coesão do material; e c) o aumento na corrosão das estruturas metálicas. A descrição do modelo apresentada é a base para a modelagem matemática e a análise de segurança dos repositórios estudados no Brasil. / The radioactive waste disposal in deep geological repositories has been studied for many countries in the last years. Cementitious materials are used in these repositories as structural material, immobilization matrix and as backfill material. The understanding of the performance of these materials is essential to ensure the safety of the installation during its life time (from thousand to hundreds of thousands of years, depending on the type of waste). This works aims at modeling the long-term performance of Portland cement and study the influence of many environmental factors in the hydration and evolution of this material. The modeling approached the cement hydration in the conditions expected in the repository and the effects of these factors on cement mechanical, mineralogical and morphological properties. The environmental factors considered relevant was: high temperature and pressure, the penetration of groundwater containing aggressive chemical ions, and a radiation field from the waste. Degradation accelerated tests were done to corroborate with the descriptive model. It was observed a synergism between some factors on the cement degradation, as the influence of temperature and radiation field in some deleterious reactions in the material. The results of modeling pointed to three main causes of engineered barrier failure: a) the formation of a preferential pathway; b) loss of resistance and cohesion in the material; and c) the increase in the metallic structures corrosion process. The descriptive model is the basis for a mathematical modeling and to perform the safety assessment of the repositories studied in Brazil.

Fault zones are potential paths for release of radioactive nuclides from radioactive-waste repositories in granitic rock. This research considers detailed maps of en echelon fault zones at two sites in southern Sweden, as a basis for analyses of how their internal geometry can influence groundwater flow and transport of radioactive nuclides. Fracture intensity within these zones is anisotropic and correlated over scales of several meters along strike, corresponding to the length and spacing of the en echelon steps. Flow modeling indicates these properties lead to correlation of zone transmissivity over similar scales. Intensity of fractures in the damage zone adjoining en echelon segments decreases exponentially with distance. These fractures are linked to en echelon segments as a hierarchical pattern of branches. Echelon steps also show a hierarchical internal structure. These traits suggest a fractal increase in the amount of pore volume that solute can access by diffusive mass transfer, with increasing distance from en echelon segments. Consequences may include tailing of solute breakthrough curves, similar to that observed in underground tracer experiments at one of the mapping sites. The implications of echelon-zone architecture are evaluated by numerical simulation of flow and solute transport in 2-D network models, including deterministic models based directly on mapping data, and a statistical model. The simulations account for advection, diffusion-controlled mixing across streamlines within fractures and at intersections, and diffusion into both stagnant branch fractures and macroscopically unfractured matrix. The simulations show that secondary fractures contribute to retardation of solute, although their net effect is sensitive to assumptions regarding heterogeneity of transmissivity and transport aperture. Detailed results provide insight into the function of secondary fractures as an immobile domain affecting mass transfer on time scales relevant to field characterization and repository safety assessment. In practical terms, secondary fractures in these en echelon zones are not indicated to limit release of radiation to the surface environment, to a degree that is significant for improving repository safety. Thus en echelon zones are to be regarded as detrimental geologic features, with potentially complex transport behavior which should be considered in the interpretation of in-situ experiments. / Graduation date: 2005

Coupled Thermo-Hydro-Mechanical (THM) behavior in geological porous media has been a subject of great interest in many geoengineering disciplines. Many attempts have been made to develop numerical prediction capabilities associated with topics such as the movement of pollutant plumes, gas injection, energy storage, geothermal energy extraction, and safety assessment of repositories for radioactive waste and spent nuclear fuel. This thesis presents a new numerical modeling approach and a new computer code for simulating coupled THM behavior in geological porous media in general, and compacted bentonite clays in particular, as buffer materials in underground radioactive waste repositories. New governing equations were derived according to the theory of mixtures, considering interactions among solid-phase deformation, flows of water and gases, heat transport, and phase change of water. For three-dimensional problems, eight governing equations were formulated to describe the coupled THM processes. A new thermal conductivity model was developed to predict the thermal conductivity of geological porous media as composite mixtures. The proposed model considers the combined effects of solid mineral composition, temperature, liquid saturation degree, porosity and pressure on the effective thermal conductivity of the porous media. The predicted results agree well with the experimental data for MX80 bentonite. A new water retention curve model was developed to predict the suction-saturation behavior of the geological porous media, as a function of suction, effective saturated degree, temperature, porosity, pore-gas pressure, and the rate of saturation degree change with time. The model was verified against experimental data of the FEBEX bentonite, with good agreement between measured and calculated results. A new finite element code (ROLG) was developed for modeling fully coupled thermo-hydro-mechanical processes in geological porous media. The new code was validated against several analytical solutions and experiments, and was applied to simulate the large scale in-situ Canister Retrieval Test (CRT) at Äspö Hard Rock Laboratory, SKB, Sweden, with good agreement between measured and predicted results. The results are useful for performance and safety assessments of radioactive waste repositories. / QC20100720 / THERESA

The decision to bury high level nuclear wastes in deep geological formations led to the study of the Hanford Nuclear Reservation as one of three possible sites for the first nuclear waste repository in the United States. To adequately evaluate the environmental impact of siting nuclear waste repositories in basalt aquicludes, it is essential to know the effects on parameter identification algorithms of thermal gradients that exist in these basaltic aquicludes. Temperatures of approximately 60° C and pressures of approximately 150 atms can be expected at potential repository sites located at depths of approximately 1000m. The phenomenon of over-recovery has been observed in some pumping tests conducted at the Hanford Nuclear Reservation. This over-recovery phenomenon may possibly be due to variations in the fluid density caused by thermal gradients. To asses the potential effects of these thermal gradients on indirect parameter identification algorithms, a systematic scaling of the governing field equations is required in order to obtain dimensionless equations based on the principle of similarity. The constitutive relationships for the specific weight of the fluid and for the porosity of the aquiclude are assumed to be exponentially dependent on the pressure gradient. The dynamic pressure is converted to the piezometric head and the flow equation for the piezometric head is then scaled in radial coordinates. Order-ofmagnitude estimates are made for all variables in unsteady flow for a typical well test in a basaltic aquiclude. Retaining all nonlinear terms, the parametric dependency of the flow equation on the classical dimensionless thermal and hydraulic parameters is demonstrated. These classical parameters include the Batchelor, Fourier, Froude , Grashof, and Reynolds Numbers associated with thermal flows. The flow equation is linearized from order-of-magnitude estimates based on these classical parameters for application in the parameter identification algorithm. Two numerical solutions are presented which predict hydraulic head given a continuous set of flow parameters. The first solution uses a totally numerical finite difference scheme while the second combines an analytical solution with a numerical solution. A radial coordinate system is utilized for describing an anisotropic confined aquifer. The classical inverse parameter identification problem is solved using an indirect method. This method is based on the minimization of a objective function or error criterion consisting of three parts: 1) least-squares error of head residuals; 2) prior information of flow parameters; and 3) regularization. An adjoint equation is incorporated into the method to eliminate the need to differentiate the heads with respect to the parameters being identified, increasing the stability of the algorithm. Verification of the parameter identification algorithm utilizes both "synthetic", computed generated input data and field data from a well test for a confined aquifer within the Columbia Plateau near Stanfield, Oregon. The method used is found to give parameter estimates which are both stable and unique. / Graduation date: 1992

Reactive transport modelling has wide applications in geosciences. In the field of hydrogeology, it has been utilised to simulate the biogeochemical processes that disperse and degrade contaminants in the aquifer. For geotechnical applications, such as geological CO2 sequestration, the reaction of CO2 with the ambient saline aquifer determines the final success of storage. In a radioactive waste repository, scientists rely on reactive transport models to predict the mobilisation of hazardous radionuclides within space and time. In this work, the multi-component mass transport code OpenGeoSys, was coupled with two geochemical solvers, the Gibbs Energy Minimization Selektor (GEM) and the Biogeochemical Reaction Network Simulator (BRNS). Both coupled codes were verified against analytical solutions and simulation results from other numerical models. Moreover, the coupling interface was developed for parallel simulation. Test runs showed that the speed-up of reaction part had a very good linearity with number of nodes in the mesh. However, for three dimensional problems with complex geochemical reactions, the model performance was dominated by solving transport equations of mobile chemical components. OpenGeoSys-BRNS was applied to a two dimensional groundwater remediation problem. Its calculated concentration profiles fitted very well with analytical solutions and numerical results from TBC. The model revealed that natural attenuation of groundwater contaminants is mainly controlled by the mixing of carbon source and electron donor. OpenGeoSys-GEM was employed to investigate the retardation mechanism of radionuclides in the near field of a nuclear waste repository. Radium profiles in an idealised bentonite column was modelled with varying clay/water ratios. When clay content is limited, Ba-Sr-Ra sulfate solid solutions have a very strong retardation effect on the aqueous radium. Nevertheless, when clay mineral is abundant, cation exchange sites also attract Sr and Ba, thus dominates the transport of Ra.

The Koongarra uranium deposit is hosted by quartz-chlorite schists. A conceptual model for the hydrogeology of the deposit is proposed on the basis of lithologic criteria and limited hydraulic testing. Water-level and aquifer-test data are presented that indicate the deposit lies within a partially confined, heterogeneous, anisotropic fractured-rock aquifer. The aquifer is dynamic with annual, diurnal, and semidiurnal water-level fluctuations. The results of aquifer tests indicate a high degree of connectivity in the aquifer. Fracture-dominated flow is observed in some tests, but the overall aquifer response appears to be that of an equivalent porous medium. A homogeneous, anisotropic model is used to estimate the transmissivity tensor for subregions of the aquifer. Anisotropy is well-developed with north- to east-northeast-oriented principal transmissivities. Northeast directions represent large-scale drawdown patterns and are subparallel to bedrock structure and the Koongarra fault. Northerly directions are localized and may reflect a less extensive fracture fabric or a flexure in the bedrock foliation.

Methods for the determination of the actinide elements in water, biological, soil and sediment samples have been developed using on-line solid phase extraction and high performance liquid chromatography (HPLC) coupled with inductively coupled plasma mass spectrometry (ICP-MS). Initial applications utilised a commercially available resin, namely TRU-Spec resin, for efficient removal of the matrix prior to elution of uranium and thorium analytes. Comparative analyses of reference materials and natural water samples from Plymouth and Dartmoor demonstrated significant improvement in precision and speed of analysis by using TRU-Spec coupled to ICP-MS compared with alpha spectrometry. Further applications of the TRU-Spec resin for the determination of the transuranic actinide elements neptunium, plutonium and americium, resulted in the successful determination of 239Pu and 237Np in biological reference materials. Detection limits were 700, 850, and 600 attograms (ag) for 237Np, 233Pu, and 241Am, respectively, for a 0.5 ml sample injection, and better than 200 ag/g with 50 ml pre-concentration when sector field (SF) ICP-MS was used. A method for the selective sequential elution of uranium and plutonium was also developed to facilitate the determination of 239Pu without interference due to the 238U1H+ polyatomic ion, caused by high concentrations of 238U in sediment samples. Investigations were performed into the use of a polymeric substrate, which was dynamically coated with chelating dyes such as xylenol orange and 4-(2-pyridylazo) resorcinol, and a silica substrate coated with permanently bonded iminodiacetic acid. The latter was used for the successful determination of uranium and thorium in certified reference material waters. However, the column was found to have a high affinity for iron, making it unsuitable for the determination of the actinides in soil and sediment samples. Subsequently, a polystyrene substrate which was dynamically coated with dipicolinic acid was used for HPLC coupled with SF-ICP-MS. Using this column it was possible to separate the various actinides from each other and from the matrix. In particular, it was possible to separate plutonium and uranium to facilitate interference-free determination of the former. The column also exhibited some selectivity for different oxidation states of Np, Pu and U. Two oxidation states each for plutonium and neptunium were found, tentatively identified as Np(V) and Pu(III) eluting at the solvent front, and Np(IV) and Pu(IV) eluting much later. Detection limits were 12, 8, and 4 fg for 237Np, 239Pu, and 241Am, respectively, for a 0.5 ml injection, and the system was successfully used for the determination of 239Pu in water, biological and soil reference materials.

No description available.